ML17328A879
| ML17328A879 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/30/1991 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 AEP:NRC:0773AL, AEP:NRC:773AL, TAC-77240, TAC-77241, NUDOCS 9102050301 | |
| Download: ML17328A879 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9102050301 DOC.DATE: 91/01/30 'OTARIZED: NO DOCKET FACIL:50.-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 6
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 6
05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R
MURLEY,T.E.
Document Control Branch (Document Control Desk)
I
SUBJECT:
Responds to 901214 ltr re emergency response capability 6
conformance to Reg Guide 1.97.Summary of upgrade to presently installed wide-range steam generator level indication encl.
DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ENCL 2 SIZE:
TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33 NOTES:
D RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T.
INTERNAL: NRR/DL
~FB11 R
G FILE EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD OC/LFMB RES/DS IR/EIB NSIC COPIES LTTR ENCL 1
1 1
0 1
1 1
1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL 9
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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 W
AEP:NRC'0773AL TAC NOS.
77240 and 77241 Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 UPGRADE OF WIDE-RANGE STEAM GENERATOR WATER LEVEL INSTRUMENTATION PER SUPPLEMENTAL SAFETY EVALUATION REPORT DATED DECEMBER 14, 1990 U,
ST Nuclear Regulatory Commission Document Control Desk Washington, D.
C.
20555 ATTN:
T.
E. Murley January 30, 1991
Dear Dr. Murley:
This letter responds to your December 14, 1990 letter concerning our emergency response capability and conformance to Regulatory Guide 1
~ 97.
Your letter states that we should install wide-range steam generator level instrumentation that complies with the Category 1
criteria of Regulatory Guide 1.97, 10 CFR 50.49, and Regulatory Guide 1.100.
We are proposing to upgrade our presently installed wide-range steam generator level indication consistent with the previously upgraded Category 1, Regulatory Guide 1.97 instrumentation.
The Safety Evaluation Report attached to your December 14, 1990 letter concurs that this design and its deviations and justifications are acceptable under the guidance provided in Regulatory Guide 1.97.
A summary of this upgrade, provided in the same format as our previous Regulatory Guide 1.97 submittals, is shown in the attachment.
Details of the above proposal were presented to your staff on January 24, 1991.
We also presented our schedule for the upgrade Although we are anxious to complete this upgrade, an actual walkdown of the in-containment areas will have to be performed before the necessary detailed installation drawings can be generated.
The detailed installation drawings are necessary for the various crafts to fabricate and assemble as many of the components as possible prior to entry into containment and, of course, for actual installation.
We have estimated that an outage.
i10ZO5OSOi PDR ADOCK P
9i0130 05000315 PDR (09
Dr. T. E. Murley AEP:NRC:0773AL of four to six weeks for each unit will be needed to perform the walkdowns and associated preliminary in-containment design activities.
We are presently scheduling these walkdowns for the next refueling outages (1992) for both units.
The actual upgrade installation would then be performed during the following refueling outages, currently anticipated to start in late 1993.
We concur with the staff's recommendation that we be prepared to start the containment walkdowns earlier if an unscheduled outage occurs.
Our ability to complete such a walkdown, however, would be a function of the length of the unscheduled outage and whether or not the necessary areas are accessible.
J This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, Alex ch Vice President MPA/eh Attachment cc:
D. H. Williams, Jr.
A. A. Blind - Bridgman J
~
R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector
- Bridgman
Attachment to AEP:NRC:0773AL t
Page 1 of 1 Item No.
D-15 Purpose Variable Cat.
Secondary S/G Level 1
System (Steam Generator)
Tag Nos.
BLI-110,
-120,-130
-140 Range From 12" above tube sheet to separators E
S Q
S P
Q 0
A F
S A
A A
A A
Display Location Control Room Panel SG Remarks/Action Schedule Required
-- Ul U2 None required, N/A N/A see footnotes (i) & (oo)
(Deviation No. DV-ll)
Re-vised D-15 Secondary System (Steam Generator)
S/G Level 1
BLI-110,
-120,-130
-140 From 12" above tube sheet to separators A
A A
A A
Control Room Panel SG Install seis-1993RF 1993RF mically quali-fied control room indicators and recorders.
Re-route cable outside of control room area to provide separation.
- Relocate, re-tube, and revise cable routing for level transmitters in--
side containment to provide seismic and environmental qualification..
(Deviation Nos.
DV-1, DV-2, DV-3, and DV-4*).
- Deviations DV-1, DV-2, DV-3, and DV-4 are explained in our submittal AEP:NRC:0073AB dated October 5, 1988.